Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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Numerical prediction of a flashing flow of saturated water at high pressure

  • Jo, Jong Chull (Korea Institute of Nuclear Safety, Reactor System Evaluation Dept.) ;
  • Jeong, Jae Jun (Pusan National University, School of Mechanical Engineering) ;
  • Yun, Byong Jo (Pusan National University, School of Mechanical Engineering) ;
  • Moody, Frederick J. (Consultant)
  • Received : 2018.02.20
  • Accepted : 2018.06.03
  • Published : 2018.10.25
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Abstract

Transient fluid velocity and pressure fields in a pressurized water reactor (PWR) steam generator (SG) secondary side during the blowdown period of a feedwater line break (FWLB) accident were numerically simulated employing the saturated water flashing model. This model is based on the assumption that compressed water in the SG is saturated at the beginning and decompresses into the two-phase region where saturated vapor forms, creating a mixture of steam bubbles in water by bulk boiling. The numerical calculations were performed for two cases of which the outflow boundary conditions are different from each other; one is specified as the direct blowdown discharge to the atmosphere and the other is specified as the blowdown discharge to an extended calculation domain with atmospheric pressure on its boundary. The present simulation results obtained using the two different outflow boundary conditions were discussed through a comparison with the predictions using a simple non-flashing model neglecting the effects of phase change. In addition, the applicability of each of the non-flashing water discharge and saturated water flashing models for the confirmatory assessments of new SG designs was examined.

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